leader project overview 3 th leader international workshop analysis and design issues of lfr reactor...

LEADER Project Overview

3th LEADER International WorkshopAnalysis and design issues of LFR reactor concept: ALFREDPisa, 4th -5th September 2012; Bologna, 6th -7th September 2012

Luigi Mansani

[email protected]

3th LEADER International Workshop; Pisa, 4th -5th September 2012; Bologna, 6th -7th September 2012

Introduction

Nuclear Energy Sustainability

Lead cooled Fast Reactors – Why?

FP7 LEADER Project

Roadmap towards an industrial LFR fleet in Europe

ALFRED (Implementation schedule, design guideline, configuration) and ELFR (configuration)

Some important facts

SUMMARY


Introduction - Generation IV Goals & Concepts

GENERATION IV SYSTEMS ACRONYMSodium-Cooled Fast Reactor SystemSFRGas-Cooled Fast Reactor SystemGFRLead-Cooled Fast Reactor SystemLFRMolten Salt Reactor System

MSRSupercritical-Water-Cooled Reactor System SCWRVery-High-Temperature Reactor SystemVHTR

GENERATION IV GOALS

Sustainability

Safety & Reliability

Economics

Proliferation Resistance & Physical Protection


European framework and context

• European energy policy, aiming at fulfilling the “20-20-20” strategy by 2020, relies on a wide implementation of nuclear technologies, including a new Generation of Fast Neutron Reactors oriented to the sustainability of nuclear energy through the actual closure of the fuel cycle

• The Strategic Research Agenda (SRA) of the Sustainable Nuclear Energy Technology Platform (SNE-TP) has selected three Fast Neutron Reactor systems (SFR, LFR and GFR) as a key structure in the deployment of sustainable nuclear fission energy

• Among the technologies under investigation in Europe Lead-cooled Fast Reactors (LFRs) represent one of the promising solutions, candidate as an alternative to the reference technology, based on Sodium-cooled Fast Reactors (SFRs)


Fast Neutron Reactorsin the frame of the

European Sustainable Nuclear Industrial Initiative (ESNII)

ESNII* Roadmap from the Concept Paper

(*) ESNII will address the need for demonstration of Gen-IV Fast Neutron Reactor technologies, together with the supporting research infrastructures, fuel facilities and R&D work All documents are available for download on www.snetp.eu

http://www.snetp.eu/

http://www.snetp.eu/www/snetp/images/stories/Docs-VisionReport/sne-tp_vision_report_eur22842_en.pdf


Sustainability:Partitioning and Transmutation (P&T)

The radio-toxicity of the fission products dominates the total radio-toxicity during the first 100 years and reaches the uranium ore mine level at about 300 years

The long-term radio-toxicity is dominated by the actinides (mainly by the Pu and Am isotopes) and the uranium ore mine level is reached only after more than 120,000 years

By recycling and then ‘burning’ all the MA, the period over which high-level radioactive waste remains hazardous could theoretically be reduced from hundreds of thousands of years down to a few hundred years


Strategy for Sustainability of Nuclear Energy

Present known resources of Uranium represent about 100 years of consumption with the existing reactor fleet

Fast neutron reactors with closed fuel cycle have the potential: to multiply by a factor 50 to 100 the energy output from a given amount of uranium (with

a full use of U238), To improve the management of high level radioactive waste through the transmutation of

minor actinides to provide energy for the next thousand years with the already known uranium resources

Both fast spectrum critical reactors and sub-critical ADS are potential candidates for dedicated transmutation systems

Critical reactors, however, loaded with fuel containing large amounts of MAs pose safety problems caused by unfavourable reactivity coefficients and small delayed neutron fraction

– Core fuelled with only MA (Uranium free) has no Doppler nor Delayed Neutrons


Sustainability:Example of Closed Fuel Cycle in Fast Reactors

LFR can be operated as adiabatic: Waste only FP, feed only Unat/dep

Pu vector slowly evolves cycle by cycle MA content increases and its composition drift in the time LFR is fully sustainable and proliferation resistant (since the start up) Pu and MA are constant in quantities and vectors Safety - main feedback and kinetic parameters vs MA content

Fabrication LFRAdiabatic

Reprocessing

All Actinides (Expected MA: 1% of which 20% Cm)

MOX first loads(U:82.5%; Pu: 17.5%)

Unat/dep: 1g/MWD+ reintegration of losses

FP: 1g/MWD + losses

MOX equilibrium(U: 82%; Pu: 17%; MA: 1%)


Why LEAD? – Some Advantages

Lead does not react with water or airSteam Generators installed inside the Reactor Vessel

Very high boiling point (1745°C ), very low vapor pressure (3 10-5 Pa @ 400 °C)Reduced core voiding reactivity risk

Lead has a higher density than the oxide fuelNo need for core catcher (molten clad and fuel float)

Lead is a low moderating medium and has low absorption cross-section.No need of compact fuel rods (large p/d defined by T/H) Very low pressure losses (1 bar for core, 1.5 bar for primary loop)Very high primary natural circulation capability natural circulation DHR

LEAD COOLANT PASSIVE SAFETY


Why LEAD? – Not Only Advantages

High Lead melting point (~ 327 °C) – assure Lead T above 340-350 °C

Overcooling transient (secondary side) may cause Lead freezing

Corrosion / erosion of structural materials - Slugging of primary coolant

Seismic risk due to large mass of lead

in-service inspection of core support structures

fuel loading/unloading management by remote handling

Steam Generator Tube rupture inside the primary system

Flow blockage and mitigation of core consequences


Why LEAD? – Not Only Advantages

High Lead melting point (~ 327 °C) – assure Lead T above 340-350 °Cheating system, design and operating procedures

Overcooling transient (secondary side) may cause Lead freezingFW requirement – diversification and redundancy – Really a

safety issue?Corrosion / erosion of structural materials - Slugging of primary coolant

Coatings, oxygen control, limit flow velocity (Russian approach)Strategy at low oxygen content (alternative approach)

Seismic risk due to large mass of lead2-D seismic isolators, vessel hanged, specific design (EU FP7

SILER project)in-service inspection of core support structures

Similar to other HLM reactors but high T, all components replaceable

fuel loading/unloading by remote handlingDevelop appropriate cooling system (active passive back-up)

Steam Generator Tube rupture inside the primary systemShow no effect on core, provide cover rupture disks to limit max

pressureFlow blockage and mitigation of core consequences

Hexagonal wrapped FAs – outlet temperature continuous monitoring

Full unprotected flow blockage causes cladding damages to a max of 7 FAs

PROVISIONS


The FP7 LEADER Project

The first step in the development of a Lead Cooled Critical Fast Reactor in Europe started in 2006 with the EU - FP6 ELSY project, on the basis of previous projects already carried out in the frame of projects dedicated to Lead-Bismuth/Lead cooled Accelerator Driven Systems (XT-ADS, EUROTRANS etc.)

On March 2010 a first reference configuration of an industrial size (600 MWe) LFR was available.

On April 2010 the LEADER project started its activities with the main goal to:

• Develop an integrated strategy for the LFR development

• Improve the ELSY design toward a new optimized conceptual configuration of the industrial size plant, the ELFR conceptual design.

• Design a scaled down reactor, the LFR demonstrator – ALFRED, using solutions as much as possible close to the adopted reference conceptual design but considering the essential need to proceed to construction in a short time frame.


The FP7 LEADER Project

Conceptual Design for Lead Cooled Fast Reactor Systems 16 European Organization are participating to the project Project Coordinator - Ansaldo Nucleare 3 year Project (2010-2013), started April 2010

LEADER Project Work Packages:WP1 - SCK CEN : Design Objectives and SpecificationWP2 - ENEA : Core designWP3 - ANSALDO: Conceptual designWP4 - EA : Instrumentation, control/protection systems WP5 - KIT-G : Safety and transient analysisWP6 - KIT-G : Lead TechnologyWP7 - KTH : Education and Training

http://www.agh.edu.pl/

http://www.leader-fp7.eu/PublicPages/consortium_partners/P04-CIRTEN.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P06-EA.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P07-ENEA.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P08-KIT-G.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P09-INR.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P10-JRC.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P11-KTH.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P12-NRG.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P13-PSI.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P14-SCK-CEN.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P15-SRS.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P16-UJV.htm

http://www.leader-fp7.eu/PublicPages/consortium_partners/P17-UNIBO.htm



• The main drawback facing the industrial deployment of a LFR fleet in Europe is the lack of operational experience

• A satisfactory technological readiness has been achieved in Russia in the past century driven by military research

• To fill the technology gap in Europe requires the setting up of a complete R&D roadmap, in analogy with what has been done in France for the development of the SFR technology chain, whose readiness is almost proven

Nuclear submarine 705 serial

(1976-1996)



For the demonstration of the LFR technology chains, further facilities (either existing or under construction) are required to provide the overall frame for LFR technology development, like: all the existing and planned EU lead labs focused on thermal/hydraulics,

materials development and corrosion testing; the zero-power facility Guinevere, already operating in Mol, Belgium, the irradiation facility and pilot plant MYRRHA, to be built and operated in

Mol and, the European training facility ELECTRA, planned for realization in Sweden

Guinevere MYRRHA ELECTRA



The LFR development roadmap towards the industrial deployment of a fleet of European LFRs, requires: first a Demonstrator reactor (ALFRED) for proving the viability of reliable

electricity production for LFR systems – 125 MWe second a Prototype reactor (PROLFR) is envisaged for testing the scaling

laws at an intermediate step according to a common approach focused both on plant size and representativeness of the target reference system – 300÷400 MWe

third a First-Of-A-Kind (ELFR-FOAK) representative of a commercial ELFR fleet – 600 MWe


ALFRED - Implementation schedule

The realization of ALFRED will allow:

the European scientific nuclear community to maintain the leading position in fast reactors design, construction and licensing,

the industries to advance in the field of fast reactor components and systems design and manufacturing, preparing to the advent of a new Generation of nuclear systems for the sustainable energy future of Europe

ALFRED is a Fundamental Step in the Development of Lead Fast Reactor

ALFRED Implementation scheduleconsortium

Basic Design, Siting and

pre-licensing

Detailed design&

licensingconstruction

Conceptual design

(LEADER)


ALFRED - Design Guidelines

ALFRED will be connected to the electrical grid Power close to 125 MWe (300 MWth)

The LFR Demonstrator design should be based as much as possible on available technology to speed up the construction time

Design solution (especially for Safety and Decay Heat Removal function) should be characterized by very robust and reliable choices to smooth as much as possible the licensing process

Decay Heat Removal System based on passive technology to reach the expected high Safety level

DHRs based on Active actuation and Passive operation


MAIN COOLANT PUMP

REACTOR VESSEL SAFETY VESSEL

FUEL ASSEMBLIES

STEAM

GENERATOR

STEAM

GENERATOR MAIN COOLANT PUMP

REACTOR CORE

ALFRED - Reactor Configuration

Power: 300 MWthPrimary cycle: 400-480 °CSecondary cycle: 335-450 °C


ELFR - Reactor Configuration

Power: 1500 MWthPrimary cycle: 400-480 °CSecondary cycle: 335-450 °C

• Pumps integrated in the SGs• Spiral SGS (8) – once through• Hexagonal Wrapped FAs• FAs extended to cover gas• Core Bottom grid• Inner shroud – lateral restraint• FAs weighted down by Tungsten

ballast (pumps off)• FAs kept in position by top springs

(pumps on)• 4 Isolation condenser connected to

SGs (DHR1)• 4 Dip coolers immersed in the main

vessel (DHR2)


Parameter ELFR ALFRED

Primary Coolant Pure Lead

Electrical Power/Efficiency, MWe/% 632 / 42 125 / 41

Primary System Pool type, Compact

Primary Coolant Circulation: Normal operation

Emergency conditionsForced by mechanical pumps

Natural

Core Inlet/outlet Temperature, °C 400 / 480

Fuel Assembly Hexagonal, wrapped, weighted down by ballast with pumps off, Forced by springs with pumps on

Max Clad Temperature, °C 550

Max. core pressure drop, MPa 0.1 (30 min grace time for ULOF)

1st System for Shutdown/control Buoyancy Absorbers Rods: control/shutdown system passively inserted from core bottom

2nd System for Shutdown Pneumatic Inserted Absorber Rods: shutdown system passively inserted from core top

Secondary System Pressure/steam temp, MPa / °C 18 / 450

Steam generators integrated in the reactor vessel Spiral type integrated in the reactor vessel Double wall Bayonet tubes

DHR System 2 Passive DHRs (Actively actuated, Passively operated) DHR N°1 based on ISOLATION CONDENSER concept; DHR N°2 based on deep cooler

2 Passive DHRs (Actively actuated, Passively operated) based on ISOLATION CONDENSER concept

Main Parameters


• GUINEVERE is operating

• FEED contract for MYRRHA – Offers delivered

• Experimental work on-going, spread over EU research Labs

• An MOU between Romania/Italy Organizations has been signed in February 2012 to define the steps and rules to be followed to form an international consortium for ALFRED Design and Construction. Intended location of ALFRED is Romania

• Romania’s Prime Minister, Mr. Victor Ponta, participating to “Nuclear 2012” hosted by INR in May, has acknowledged the importance of ALFRED and committed, on behalf of his Government, to ask the Commission to host ALFRED in Romania

• STRONG SYNERGIES have been identified between SFR and LFR technologies (HeliMNet meeting – Aix en Provence – October 2011 – www.helimnet.eu)

Last but not least ….some important facts for ALFRED


GIF LFR Reference Concepts

CLOSURE HEAD

CO2 INLET NOZZLE (1 OF 4)

CO2 OUTLET NOZZLE (1 OF 8)

Pb-TO-CO2 HEAT EXCHANGER (1 OF 4)

ACTIVE CORE AND FISSION GAS PLENUM

RADIAL REFLECTOR

FLOW DISTRIBUTOR HEAD

FLOW SHROUDGUARD VESSEL

REACTOR VESSEL

CONTROL ROD DRIVES

CONTROL ROD GUIDE TUBES AND DRIVELINES

THERMAL BAFFLE

SSTAR (10 - 100 MWe) ELFR (600 MWe)BREST 300 (300 MWe)

LFR MOU signed by Japan and Euratom October 2010LFR MOU signed by Russia July 2011

Presentation to the GIF Symposium in San Diego – November 2012Development of a position paper on LFR safetySystem Research Plan will be revised – expected issue end of 2012 LFR Reference concepts: SSTAR, BREST 300, ELFR

THANK YOU FOR YOUR ATTENTION

leader project overview 3 th leader international workshop analysis and design issues of lfr reactor...

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